ML19305B172
| ML19305B172 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 10/16/1979 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19305B158 | List: |
| References | |
| 50-324-79-34, 50-325-79-35, NUDOCS 8003190262 | |
| Download: ML19305B172 (1) | |
Text
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OCT 2 61979 APPENDIX A NOTICE OF VIOLATION Carolina Power and Light Company License Nos. DPR-71 Brunswick Units 1 and 2
& DPR-62 Based on the NRC inspection July 27 - August 31, 1979, certain of your activities were apparently not conducted in full compliance with NRC requirements as indicated below. These items have been categorized as described in correspondence to you dated December 31, 1974.
A.
As required by Section (e) of 10 CFR 20.203, which states, "Each area or room in which licensed material is used or stored and which contains any radioactive material (other than natural uranium or thorium) in an amount exceeding 10 times the quantity of such material specified in Appendix C of this part shall be conspicuously posted with a sign or signs bearing the radiation caution symbol and the words: " CAUTION - RADI0 ACTIVE MATERIAL" or
" DANGER - RADI0 ACTIVE MATERIAL".
Contrary to the above, unattended radioactive material was found stored in Warehouse "C" on August 24, 1979, and no signs were posted at the entrance or access points. This condition was later corrected by the installation of proper signs at the entrance points to the warehouse, and verified by the inspector on August 28, 1979.
This 'is a deficiency and is applicable to Units 1 and 2.
B.
As required by 10 CFR 50 Appendix B, Criteria V, activities affecting quality shall be prescribed by documented instructions and procedures of a type appropriate to the circumstance. ANSI N18.7-1972, as committed to by the Carolina Power and Light Company (CP&L) Quality Assurance Program, in Section 5.4 requires applicable procedures shall be reviewed following any modifications to a system. This requirement has been implemented by the licensee's Procedures Preparation Manual, Section 10.
Contrary to the above, reactor vessel level instrument NO26A was returned to service following a modification on July 28, 1979, using revision 4 of PT 53.3, which did not contain the correct procedure for valving in a differential pressure sensor with she low pressure tap piped to the reference leg.
This is a deficie.,cy and is applicable to Unit 1.
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